Corrosion behavior of different parts of the weld of 316L/52M/A508 dissimilar metal welded joint in simulated pressurized water reactor primary water

2015 ◽  
Vol 66 (12) ◽  
pp. 1435-1444 ◽  
Author(s):  
J. Ding ◽  
Z.-M. Zhang ◽  
J.-Z. Wang ◽  
J.-Q. Wang ◽  
E.-H. Han
Keyword(s):  
Corrosion Behavior ◽  
Welded Joint ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Dissimilar Metal ◽  
Primary Water ◽  
Different Parts

Stress Corrosion Cracking Behavior of Alloy 182 Weld in Pressurized Water Reactor Primary Water Environment at 325ºC

CORROSION ◽  
2011 ◽  
Vol 67 (8) ◽  
pp. 085004-1-085004-9 ◽  
Author(s):  
L.I.L. Lima ◽  
M.M.A.M. Schvartzman ◽  
C.A. Figueiredo ◽  
A.Q. Bracarense
Keyword(s):  
Stress Corrosion ◽  
Oxide Layer ◽  
Stress Corrosion Cracking ◽  
Power Plants ◽  
Corrosion Cracking ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Cracking Behavior ◽  
Water Reactor ◽  
Primary Water

Abstract The weld used to connect two different metals is known as a dissimilar metal weld (DMW). In nuclear power plants, this weld is used to join stainless steel to low-alloy steel components in the nuclear pressurized water reactor (PWR). The most common weld metal is Alloy 182 (UNS W86182). Originally selected for its high corrosion resistance, it exhibited, after a long operation period, susceptibility to stress corrosion cracking (SCC) in PWR. The goal of this work was to study the electrochemical corrosion behavior and SCC susceptibility of Alloy 182 weld in PWR primary water containing 25 cm3 and 50 cm3 H2/kg H2O at standard temperature and pressure (STP). For this purpose, slow strain rate tensile (SSRT) tests and potentiodynamic polarization measurements were carried out. Scanning electron microscopy (SEM) with energy-dispersive spectrometry (EDS) was used to evaluate fracture morphology and determine the oxide layer chemical composition and morphology. The results indicated that at 325°C Alloy 182 weld is more susceptible to SCC at 25 cm3 (STP) H2/kg H2O and the increase of dissolved hydrogen decreased the crystal size of the oxide layer.

scholarly journals Corrosion Behavior of Cu Alloys in Secondary System of Pressurized Water Reactor

2012 ◽  
Vol 61 (8) ◽  
pp. 327-334
Author(s):  
Kazutoshi Fujiwara ◽  
Masafumi Domae
Keyword(s):  
Corrosion Behavior ◽  
Pressurized Water Reactor ◽  
Secondary System ◽  
Pressurized Water ◽  
Water Reactor ◽  
Cu Alloys
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